Flow-Induced Vibration Analysis of Nuclear Components

摘要

Excessive flow-induced vibration may lead to fretting-wear or fatigue problems in nuclear components. Some recent vibration problems and their solution are reviewed. The analytical and experimental techniques used to solve or preferably avoid flow-induced vibration problems are emphasized in this paper. Vibration excitation mechanisms in parallel and cross-flow and in both liquid and two-phase steam-water flow will be discussed. These vibration excitation mechanisms and the structural dynamics of nuclear components are formulated in analytical models. This is illustrated by the application of a computer model to analyse steam generator designs. Current studies related to flow-induced vibration are reviewed. Among these are: 1) the in-reactor vibration behaviour of nuclear fuel elements, 2) the prediction of vibration-fretting damage for heat exchanger tube materials and 3) the damping of wind-induced vibration of heavy water plant structures. (Atomindex citation 11:514092)